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Shurong Ding

Observed names: S. Ding, Shu-Rong Ding
Observed institutions: Tianjin University, Chinese Academy of Sciences, Fudan University, Zhengzhou University, Institute of Modern Physics, Nuclear Power Institute of China
ORCID: 0000-0002-9304-0233
Observed ORCID: 0000-0002-9304-0233
OpenAlex ID: A5101578293
Rhodamine B‐Derived Low‐Toxicity Full‐Color Carbon Dots with Wide Tunable High‐Stable Liquid‐State Lasers
2025 · Yongqiang Zhang, Xueyan Ren, et al. · Advanced Materials · 53
Adjusting TADF and Phosphorescence for Tailored Dynamic Time‐Dependent Afterglow Colored Carbon Dots spanning Full Visible Region
2025 · Yongqiang Zhang, Yue Liu, et al. · Angewandte Chemie International Edition · 52
Unveiling the photoluminescence mechanisms of carbon dots through tunable near-infrared dual-wavelength lasing
2024 · Yongqiang Zhang, Shurong Ding, et al. · Matter · 48
Multi-physics modeling of delayed hydride cracking in zirconium alloys
2019 · Zhongjia Xia, Jingyu Zhang, et al. · Journal of the Mechanics and Physics of Solids · 43
Simulation of the irradiation-induced thermo-mechanical behaviors evolution in monolithic U–Mo/Zr fuel plates under a heterogeneous irradiation condition
2015 · Yunmei Zhao, Xin Gong, et al. · Nuclear Engineering and Design · 39
Modifications and applications of the mechanistic gaseous swelling model for UMo fuel
2014 · Yi Cui, Shurong Ding, et al. · Journal of Nuclear Materials · 39
A new method to simulate the micro-thermo-mechanical behaviors evolution in dispersion nuclear fuel elements
2014 · Xin Gong, Yunmei Zhao, et al. · Mechanics of Materials · 39
Exploring Carbon Dots for Biological Lasers
2025 · Yongqiang Zhang, Yuzhuo Yang, et al. · Advanced Materials · 37
SiC ceramics joined with an in-situ reaction gradient layer of TiC/Ti3SiC2 and interface stress distribution simulations
2018 · Xiaobing Zhou, Zhen Liu, et al. · Ceramics International · 35
Modelling of effective irradiation swelling for inert matrix fuels
2021 · Jing Zhang, Haoyu Wang, et al. · Nuclear Engineering and Technology · 34
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A numerical method for simulating the non-homogeneous irradiation effects in full-sized dispersion nuclear fuel plates
2014 · Yunmei Zhao, Xin Gong, et al. · International Journal of Mechanical Sciences · 33
Mechanical behaviors of the dispersion nuclear fuel plates induced by fuel particle swelling and thermal effect II: Effects of variations of the fuel particle diameters
2009 · Shurong Ding, Qiming Wang, et al. · Journal of Nuclear Materials · 31
Skeleton-creep based bubble growth model and multi-scale mechanical constitutive model for U-10Mo fuels under irradiation
2023 · Xiaobin Jian, Jing Zhang, et al. · International Journal of Plasticity · 30
Modeling of irradiation-induced thermo-mechanical coupling and multi-scale behavior in a fully ceramic-microencapsulated fuel pellet
2020 · Hongyang Wei, Jing Zhang, et al. · Journal of Nuclear Materials · 28
A mesoscale stress model for irradiated U 10Mo monolithic fuels based on evolution of volume fraction/radius/internal pressure of bubbles
2019 · Xiaobin Jian, Xiangzhe Kong, et al. · Nuclear Engineering and Technology · 28
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Modeling of the heat transfer performance of plate-type dispersion nuclear fuel elements
2009 · Shurong Ding, Yongzhong Huo, et al. · Journal of Nuclear Materials · 28
A multilayer nodes update method in FEM simulation of large depth fretting wear
2013 · Lichen Tang, Shurong Ding, et al. · Wear · 25
Reliability analysis of dispersion nuclear fuel elements
2007 · Shurong Ding, Xin Jiang, et al. · Journal of Nuclear Materials · 25
Effects of irradiation on the multi-field coupling delayed hydride cracking behavior of zirconium alloys
2022 · Guochen Ding, Zhongjia Xia, et al. · Journal of Nuclear Materials · 24
Effects of irradiation hardening and creep on the thermo-mechanical behaviors in inert matrix fuel elements
2013 · Xin Gong, Shurong Ding, et al. · Mechanics of Materials · 24
Solution-Processed Near Unit Carbon Dots-Based Deep-Blue Electroluminescent Light-Emitting Diodes with External Quantum Efficiency over 10%
2025 · Boyang Wang, Jingkun Yu, et al. · Nano Letters · 23
Simulation of the fission-induced swelling and creep in the CERCER fuel pellets
2015 · Yunmei Zhao, Xin Gong, et al. · Materials & Design · 23
Further development of the fission gas swelling model for U-10Mo fuels
2022 · Xiaobin Jian, Feng Yan, et al. · Journal of Nuclear Materials · 22
Coupled effects of director orientations and boundary conditions on light induced bending of monodomain nematic liquid crystalline polymer plates
2012 · Yue You, Changwei Xu, et al. · Smart Materials and Structures · 22
An analytical solution for simulation of the fission gas behaviors with time-dependent piece-wise boundary resolution
2012 · Yi Cui, Yongzhong Huo, et al. · Journal of Nuclear Materials · 22
Works count: 130
Citation count: 1,564
H-index: 22
I10-index: 60
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